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Amend 56 to License NPF-86,revising App a TSs Re Requirements for Control Room Subsystems
	ML20216C786
Person / Time
Site:	Seabrook
Issue date:	04/09/1998
From:	Thomas C; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20216C791	List: ML20216C786; ML20216C798;
References
	NUDOCS 9804150039
	Download: ML20216C786 (10)
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t UNITED STATES g,

,g NUCLEAR REGULATORY COMMISSION l

'f WASHINGTON, D.C. 20066-0001 o

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l NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL.*

DOCKET NO. 50-443 SEABROOK STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 6 License No. NPF-86 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by North Atlantic Energy Service Corporation, et al. (the licensee), dated September 26,1997, as supplemented by letter dated March 12,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authodzed by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

' North Atlantic Energy Service Company (NAESCO)is authorized to act as the agent for: North Atlantic Energy Corporation, Canal Electric Company, Connecticut Light and Power Company, Great Bay Power l

Corporation, Hudson Light and Power Department, Massachusetts Municipal Wholesale Electric I

Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, and United Illuminating Company, and has exclusive l

responsibility and control over the physical construction, operation, and maintenance of the facility.

9804150039 900409 PDR ADOCK 05000443 p

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2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

NPF-86 is hereby amended to read as follows:

(2)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment l

No. 5 6, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No. NPF-86. NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ebb 01 0h dd9---

Cecil O. Thomas, Director Project Directorate 1-3 l

Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of issuance: April 9, 1998-

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l ATTACHMENT TO LICENSE AMENDMENT NO.5 6 FACILITY OPERATING LICENSE NO. NPF-86 l

DOCKET NO. 50-443 Replace the following pages of Appendix A, Technical Specifications, with the attached pages ss indicated. The revised pages are identified by amendment number and contain verticallines indicating the areas of change. Overleaf pages have been provided.'

Remove Insert vii' vii*

viii viii xi xi l

xii' xii' 3/4 7-15' 3/4 7-15*

3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-13 I

3/4 7-18a i

B 3/4 7-3A*

B 3/4 7-4 B 3/4 7-4 B 3/4 7-5 B 3/4 7-5 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION PAGE Containment Air Locks....................................

3/4 6-7 Internal Pressure........................................

3/4 6-9 Air Temperature..........................................

3/4 6-10 Containment Vessel Structural Integrity..................

3/4 6-11 Containment Ventilation System...........................

3/4 6-12 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.................................

3/4 6-14 Spray Additive System....................................

3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................

3/4 6-16 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................

3/4 6-18 Electric Hydrogen Recombiners............................

3/4 6-19 Hydrogen Mixing System...................................

3/4 6-20 3/4.6.5 CONTAINMENT ENCLOSURE BUILDING containment Enclosure Emergency Air Cleanup System.......

3/4 6-21

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Containment Enclosure Building Integrity.................

3/4 6-24

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Containment Enclosure Building Structural Integrity......

3/4 6-25 3/4.7 PLANT SYSTEMS j

1 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................

3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGN SETPOINT WITH IN0PERABLE STEAM LINE SAFETY VALVES DURING FOUR-LOOP 0P E RATION......................................

3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7-2 Auxiliary Feedwater System...............................

3/4 7-3 Condensate Storage Tank..................................

3/4 7-6 Specific Activity........................................

3/4 7-7 TABLE 4.7-1 SECONDARY C0OLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................

3/4 7-8 Main Steam Line Isolation Va1ves.........................

3/4 7-9 Atmospheric Relief Va1ves................................

3/4 7-10 i

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SEABROOK - UNIT 1 vii Amendment No. 14 MG 2 71992

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BASES SECTION ggfrg TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS B 3/4 4-11 i

3/4.4.10 STRUCTURAL INTEGRITY......

B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.....

B 3/4 4-16 3/4.5 EMERGFNCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS..........

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS B 3/4 5-1 1

3/4.5.4 REFUELING WATER STORAGE TANK.......

B 3/4 5 2 l

3/4.6 CONTAINMENT SYSTEMS l

3/4.6.1 PRIMARY CONTAINMENT B 3/4 6-1 l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.

B 3/4 6 3 3/4.6.3 CONTAINMENT ISOLATION VALVES B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL B 3/4 6-3 3/4.6.5 CONTAINMENT ENCLOSURE BUILDING B 3/4 6-4 3/4.7 PL ANT SYSTEMS 3/4.7.1 TURBINE CYCLE B 3/4 7-1 i

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION B 3/4 7-3 l

3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM........

B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM...............

B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK..........

B 3/4 7-3 3/4.7.6 CONTROL ROOM SUBSYSTEMS B 3/4 7-4 l

i 3/4.7.7 SNUBBERS..........

B 3/4 7-4 l

3/4.7.8 SEALED SOURCE CONTAMINATION B 3/4 7-5 l

3/4.7.9 (This specification number is not used)

B 3/4 7-5 l

3/4.7.10 AREA TEMPERATURE MONITORING B 3/4 7-5 3/4.8 EtECTRICAL POWER SYSTEMS l

l 3/4.8.1. 3/4.8.2. and 3/4.B.3 A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION B 3/4 8 1 l

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES..

B 3/4 8 3 3/4.9 REFUELING OPERATIONS I

3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 3/4.9.3 DECAY TIME................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 3/4.9.5 COMMUNICATIONS..

B 3/4 9-1 3/4.9.6 REFUELING MACHINE B 3/4 9-1 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING..

B 3/4 9-2 Amendment No. %

SEABROOK - UNIT 1 xi l

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SEABROOK - UNIT 1 3/4 7-15 Amendment No. 32,

OCT 5 1994

PLANT SYSTEMS CONTROL ROOM SUBSYSTEMS EMERGENCY MAKEUP AIR AND FILTRATION SURVEILLANCE REOUIREMENTS (Continued) b.

At least once per 18 months or (1) after any structural maintenance l

on the HEPA filter or G arcoal adsorber housings. or (2) following painting. fire or Gemical release in any ventilation zone communicating with the system by:

1)

Verifying that the filtration system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than.05% and uses the test procedure guidance in Regulatory Position C.5.a. C.5.c. and C.S.d of Regulatory l

Guide 1.52. Revision 2. March 1978* and the system flow rate is 1100 cfm 10%;

2)

Verifying. within 31 days after removal, that a laboratory

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analysis of a re]resentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978*. meets the labatatory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52. Revision 2. March 1978*. for a methyl iodide penetration of less than 1.0%: and

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3)

Verifying a system flow rate of 1100 cfm 10% during system operation when tested in accordance with ANSI N510-1980.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying.

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within 31-days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978*.

meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52. Revision 2. March 1978*. for a methyl i

iodide penetration of less than 1.0%:

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At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks, for filter CBA-F-38. is less than 2.8 inches Water Gauge while operating the system at a flow rate of 1100 cfm i 10%: and verifying that the pressure dro) across the combined HEPA filters and charcoal adsorber bancs. for filter CBA-F-8038, is less than 6.3 inches Water Gauge while operating the system at a flow rate of 1100 cfm 10%.

2)

Verifying that upon generation of an 'S' test signal. the following automatic system functions occur:

a.

The normal makeup air fan (s) trip off and the normal makeup air isolation damper (s) close:

ANSI N510-1980 shall be used in place of ANSI N510-1975 as referenced in Regulatory Guide 1.52. Revision 2.

SEABROOK - UNIT 1 3/4 7-17 Amendment No.56

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM SUBSYSTEMS AIR CONDITIONING LIMITING CONDITION FOR OPERATION 3.7.6.2 Two independent Control Room Air Conditioning Subsystems shall be OPERABLE.

APPLICABILITY: All MODES (LT10N MODES 1. 2. 3 and 4:

With one Control Room Air Conditioning Subsystem inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6:

a.

With one Control Room Air Conditioning Subsystem inoperable, restore the inoperable system to OPERABLE status wit 11n 30 days or initiate and maintain operation of the remaining OPERABLE Control Room Air Conditioning Subsystem or immediately suspend all.

o)erations involving CORE ALTERATIONS or positive reactivity

c1anges, b.

With both Control Room Air Conditioning Subsystems inoperable, or with the OPEPABLE Control Room Air Conditioning Subsystem unable to maintain temperature below the limiting equipment qualification temperature in the control room area. suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REOUIREMENTS 4.7.6.2 Each Control Room Air Conditioning Subsystem shall be demonstrated OPERABLE at least once per 92 days by verifying the ability to maintain temperature in the control room area below the limiting equipment qualification temperature for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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'SEABROOK - UNIT 1 3/4 7-1Ba Amendment No.56 t

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PLANT SYSTEMS nAsEs i

3/4.7.4 SERVICE WATER SYSTEM / ULTIMATE HEAT SINK (Continued) discussed, realignment to the service water pumphouse requires manual action maintaining the control switches in the pull-to-lock position does not change; this required action sequence.

the control switches in the pull-to-lock position during this periodPump o therefore, OPERABILITY of the service water pumps is not compromised;.

The limitations on service water pumphouse minimum water level and the requirements for cooling tower OPERABILITY are based on providing a 30-day cooling water supply to safety-related equipment without exceeding the safety related equipment design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," March 1974.

The Cooling Tower is nomally aligned to allow return flow to bypass the tower sprays and return to the basin.

In addition, the control switches for the cooling tower fans are normally maintained in the ' pull-to-lock' position.

Upon receipt of a Tower Actuation Signal, the fans and sprays are manually operated as required.

This manual operation, which is governed by procedures, ensures that ice does not buildup on the cooling tower tile fill and fans. The cooling tower basin temperature limit of 70'F provides sufficient time for manual initiation of the cooling tower sprays and fans following the design

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basis seismic event with a concurrent LOCA, during the design extreme ambient temperature conditions. Under this scenario, manual action is sufficient to 4

maintain the cooling tower basin at a temperature which precludes equipment damage during the postulated design basis event.

3/4.7.5 iTH15 SPECIFICATION NUMBER IS NOT UsED)

SEABROOK - UNIT 1 8 3/4 7-3A Amendment No. 32 OCT 5 1994

PLANT SYSTEMS BASES 3/4 7 7 SNUBBERS (Continued)

Surveillance to demonstrate OPERABILITY is by performance of the require-ments of an approved inservice inspection program.

Permanent or other exemptions.from " e surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the com-pletion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area in high temperature area.

etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

3/4.7 8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters. is based on 10 CFR 70.39(a)(3) limits for plutonium. This limitation will ensure that leakage from Byproduct. Source. and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use.

with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e.. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanin.

3/4.7.9 (This specification number is not used.)

3/4.7.10 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be-subjected to temperatures in excess of their environmental qualification temperatures.

Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY. The temperature limits include an allowance for instrument error of 4.5 F.

SEABROOK - UNIT 1 B 3/4 7-5 Amendment No. 48,56

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ML20216C786

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